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Exhaust behavior of tritium from the large helical device in the first deuterium plasma experiment
http://hdl.handle.net/10655/00012516
http://hdl.handle.net/10655/000125163d32f748-0476-4839-b168-b98c005e88e6
名前 / ファイル | ライセンス | アクション |
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JNST57(12)_pp1297-1306 (2.5 MB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2021-06-23 | |||||
タイトル | ||||||
タイトル | Exhaust behavior of tritium from the large helical device in the first deuterium plasma experiment | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | large fusion test device | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | wall conditioning operation | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritum release | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | plasma exhaust gas | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritumu chemical forms | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritumu balance | |||||
キーワード | ||||||
主題Scheme | Other | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
著者 |
Tanaka, Masahiro
× Tanaka, Masahiro× Suzuki, Naoyuki× Kato, Hiromi |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The tritium exhaust behavior from the Large Helical Device (LHD) was observed in the first deuterium plasma experimental campaign. Tritium in the exhaust gas was monitored at the conducted by use of the ionization chamber and water bubbler system with the discrimination of chemical forms. The observation results indicated that (i) tritium on the surface of the first wall and divertor tiles as plasma facing components was released by the hydrogen isotope exchange reaction of the glow discharge cleaning operation and the diffusion-limited process was suggested in the tritium release behavior from the bulk, (ii) the amount of tritium release from the LHD vacuum vessel was about one-third of the produced tritium and the mostly produced tritium was still retained at the end of plasma experimental campaign, (iii) the ratio of exhausted tritium from the LHD vacuum vessel was larger than that in the case of JT-60U based on the carbon materials as the plasma-facing components. It indicated that the tritium inventory would be reduced and controlled by the kind of plasma-facing materials. | |||||
書誌情報 |
Journal of Nuclear Science and Technology 巻 57, 号 12, p. 1297-1306, 発行日 2020-06-23 |
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出版者 | ||||||
出版者 | Taylor and Francis | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0022-3131 | |||||
権利 | ||||||
権利情報 | This is an Accepted Manuscript version of the following article, accepted for publication in [JOURNAL]. [INCLUDE CITATION]. It is deposited under the terms of the Creative Commons Attribution-NonCommercial License (http://creativecommons.org/licenses/by-nc/4.0/), which permits non-commercial re-use, distribution, and reproduction in any medium, provided the original work is properly cited. | |||||
情報源 | ||||||
関連名称 | This is an Accepted Manuscript of an article published by Taylor & Francis in Journal ofnNuclear Science and Technology on 23 June 2020, available online: http://www.tandfonline.com/.10.1080/00223131.2020.1782282 | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1080/00223131.2020.1782282 | |||||
関連名称 | Publisher version | |||||
著者版フラグ | ||||||
出版タイプ | AM | |||||
出版タイプResource | http://purl.org/coar/version/c_ab4af688f83e57aa | |||||
NAIS | ||||||
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